{"title":"表征核反应堆中子输运的二维时间分数中子扩散方程的高阶数值方法","authors":"Jianxiong Cao , Xiaodong Zhao , Pradip Roul","doi":"10.1016/j.nucengdes.2025.114145","DOIUrl":null,"url":null,"abstract":"<div><div>In this article, we investigate a numerical method for solving a two-dimensional time-fractional neutron diffusion equation that incorporates three Caputo fractional derivatives in time. First, the existence, uniqueness, and solution representation are established. We then develop an efficient numerical scheme using the linear Galerkin finite element method for spatial discretization and a second-order convolution quadrature for temporal discretization. Error estimates for both semidiscrete and fully discrete schemes are derived. Our proposed numerical method is demonstrated to achieve second-order convergence in both space and time. Numerical experiments are conducted to validate the theoretical results. Neutron fluxes are computed for both short and long simulation times to analyze the behavior of neutron diffusion under varying orders of the fractional derivative. Additionally, a comparison is made with the method presented in Roul et al. (2020) to highlight the advantages of our proposed approach.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"441 ","pages":"Article 114145"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"A high order numerical method for 2D time-fractional neutron diffusion equation characterizing neutron transport in nuclear reactors\",\"authors\":\"Jianxiong Cao , Xiaodong Zhao , Pradip Roul\",\"doi\":\"10.1016/j.nucengdes.2025.114145\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In this article, we investigate a numerical method for solving a two-dimensional time-fractional neutron diffusion equation that incorporates three Caputo fractional derivatives in time. First, the existence, uniqueness, and solution representation are established. We then develop an efficient numerical scheme using the linear Galerkin finite element method for spatial discretization and a second-order convolution quadrature for temporal discretization. Error estimates for both semidiscrete and fully discrete schemes are derived. Our proposed numerical method is demonstrated to achieve second-order convergence in both space and time. Numerical experiments are conducted to validate the theoretical results. Neutron fluxes are computed for both short and long simulation times to analyze the behavior of neutron diffusion under varying orders of the fractional derivative. Additionally, a comparison is made with the method presented in Roul et al. (2020) to highlight the advantages of our proposed approach.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"441 \",\"pages\":\"Article 114145\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-29\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S002954932500322X\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002954932500322X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
A high order numerical method for 2D time-fractional neutron diffusion equation characterizing neutron transport in nuclear reactors
In this article, we investigate a numerical method for solving a two-dimensional time-fractional neutron diffusion equation that incorporates three Caputo fractional derivatives in time. First, the existence, uniqueness, and solution representation are established. We then develop an efficient numerical scheme using the linear Galerkin finite element method for spatial discretization and a second-order convolution quadrature for temporal discretization. Error estimates for both semidiscrete and fully discrete schemes are derived. Our proposed numerical method is demonstrated to achieve second-order convergence in both space and time. Numerical experiments are conducted to validate the theoretical results. Neutron fluxes are computed for both short and long simulation times to analyze the behavior of neutron diffusion under varying orders of the fractional derivative. Additionally, a comparison is made with the method presented in Roul et al. (2020) to highlight the advantages of our proposed approach.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.